ML041730201
| ML041730201 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 06/02/2004 |
| From: | Conicella N Public Service Enterprise Group |
| To: | Conte R NRC/RGN-I/DRS/OSB |
| Conte R | |
| References | |
| 50-272/04-301, 50-311/04-301 | |
| Download: ML041730201 (35) | |
Text
Appendix D Form ES-D-1 Facility: SALEM 1 & 2 Scenario No.: NRC #I Op-Test No.: HOTEL Examiners: Operators:
Initial Conditions: 90% Rated Thermal Power, MOL, Equilibrium Conditions Turnover: Unit 2 is at 90% power with the following equipment is out of service: SA EDG taken 00s 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> ago for injector maintenance, 21 RHR Pump taken 0 0 s 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> ago for coupling alignment. Maintenance on both components expected to be completed 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> from now. All required surveillances are complete. Weather conditions are normal. Unit 1 is at 100% power. Hope Creek is in a refueling outage. Shift orders are to raise power to 100% at 10% per hour.
F Event Malf. No. Event Event Type* Description
I-------- N Raise Reactor Power CRSlPO R
~ ~~~ ~
RO ~ ~
2 SW0215A C 21 SW Pump Trip With Failure of 25 Service Water Pump SW0339E CRSlPO to Auto Start 3 PRO016A I Pressurizer Pressure Channel IFails Low (TS CRS)
CRSlRO 1 4 I ~~
VCOl73A I ------------- 21 Cntmt Fan Coil Unit Trip (TS CRS) 5 I CN0086 I LL I Decreasing Condenser Vacuum 6 BFOlO5A&B M Mn Feed Pumps Trip on High Exh Hood Pressure, RP0059A&B ALL A M , Pzr Safety 2PR3 Fails Open RP0058 PR0020A 7 RP318G5 C 23 Aux Building Exhaust Fan Fails to Start on SEC CRSlPO Terminate after SI flow reduction evaluation in LOCA-1
- (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Page I of 12 NUREG-I 021, Draft Revision 9
SIMULATOR SETUP INITIAL CONDITIONS I
- 1. Initialize simulator to IC-I91, 90% power, MOL, CB869 ppm
- 4. Pzr Press and Level Ch I selected for control and recorder
- 5. 21 Cntmt Fan Coil Unit running in high speed
- 6. I PZR Safety Valve 2PR3 fails open when turbine governor valve 22MS29 is 4 5 % open (MONP100~0.15)
No Description Delay Ramp Remotel Initial Final Event Value Value
- 1. AN0253, SER 253 Fails: G29 Priming Tank No No NolNo 0 1
- 2. RP0059A, Failure of Man Rx Trip No No NolNo NA True
- 3. RP0059B, Failure of Man S i l k Trip No No NolNo NA True
- 4. RP0058, Failure of Auto Rx Trip' No No NolNo NA True
- 5. RP318G5,23 AB Exh Fn Fails to Start on SEC No No NolNo NA True
- 7. SWO215A, 21 SW Pump Trip No No 1lNo NA True
- 8. PRO016A, Pzr Press Ch I (PT455) Fails Low No No 2/No NA 1700
- 9. VCOl73A, 21 Cntmt Fan Coil Unit Trip I No I No I 3lNo I True I True I IO. CN0086, Loss of Main Condenser Vacuum2 No 00:03:00 4lNo 0 50
- 11. BF0105A, 21 Stm Gen Feed Pump Trip No No 5lNo 0 3
- 12. BFOI05B, 22 Stm Gen Feed Pump Trip 00:00:07 No 5lNo 0 3
- 13. PR0020A, Pzr Safety Valve 2PR3 Fails Open No No No16 NA True Page 2 of 12 NUREG-1021, Draft Revision 9
REMOTE FUNCTION
SUMMARY
I No Description I Delay 1 Ramp I Remote
/Event I Initial Value L : I: : I
- 1. RH26D, 21 RHR Pump Bkr Control Pwr No No NoINo Off off
- 2. RH27D, 21 RHR Pump Rack Out No No NoINo Tagged Tagged
- 3. DGIOA, 2A Diesel Gen Locked Out No No NolNo Yes Yes
- 4. I DG11D, 2A DG Bkr Control Power I No I No I NolNo I off I off I I 5. I DG12D,2ADGBkrRackOut I No I No I NoINo I
~
Tagged I Tagged I RP07D, 21 MG Set Motor Bkr No No 7/NO Start stop RP08D, 22 MG Set Motor Bkr 00:00:10 No TINO Start stop PR34D, PORV Stop Valve 2PR6 Tagged No No 8lNo Untagged Tagged
- 9. CT191D, 21 CFCU 125 VDC Breaker No No 9INo On off UO OVERRIDE
SUMMARY
I I I I I I No Description Delay Ramp Remote Initial Final IEvent Value Value
- 1. 8440, OVDl RTB A Trip Switch No No NoINo off off
- 2. 8441, OVDI RTB B Trip Switch No No NoINo off off
- 3. C310,2E6D Pressure Heater Bus 480V Open No No NolNo Off off Switch
- 4. C510,2G6D Pressure Heater Bus 480V Open No No NoINo off Off Switch
- 1. Open Reactor Trip Breakers 3 minutes after directed by crew. Delete overrides on RBs, then B440, 8441, RTB "A" and "B" open switch to ON. Also, open following breakers:
RT-7, RP07D 21 Rod Drive MG Set Motor Breaker RT-7, RP08D 22 Rod Drive MG Set Motor Breaker
- 2. Once the crew has reduced reactor power by approximately 10% on decreasing vacuum, change RT-4 Final Value = 100, Ramp = 0O:OO:OO
- 3. If requested, turn power off to 2PR6 using Remote Function PR34D, PORV Stop Valve toggled to Tagged on RT-8 Page 3 of 12 NUREG-1021, Draft Revision 9
' 4. Collect trend data on the following for evaluators:
Reactor Power Turbine Generator Load (MW)
Condenser Vacuum Pressurizer pressure (not Ch I / PT455)
Page 4 of 12 NUREG-1021, Draft Revision 9
1I I Op-Test No.: 1 Scenario No.: 1 Event No.: 1 Event
Description:
Unit is at 90% power. Shift orders are t o raise power to 100% at 10% per hour.
I Time Position Applicant's Actions or Behavior CRS Directs activities associatedwith power increase
- rod motion
- dilution
-turbine loading RO Adds positive reactivity
- rod motion
- dilution (Procedure S2.OP-SO.CVC-O0OS(Q))
PO Coordinates with RO to initiate power increase
- operate turbine controls to establish loading rate (Procedure S2.OP-SO.TRB-0001 (Q)
CRS Makes necessary notifications
- load dispatcher
- operations management SIMULATOR OPERATOR:
Page 5 of 12 NUREG-1021, Draft Revision 9
Op-Test No.: I Scenario No.: 1 Event No.: 2 Event
Description:
21 SW Pump Trip With Failure of 25 SW Pump to Auto Start 1 Time I Position I ADDlicant's Actions or Behavior PO Observes alarms associated with 21 SW Pump trip (OHA B-13,8-14).
PO Determines that 25 SW Pump has failed to auto start. Recommends manually starting an idle pump.
CRS Directs manual start of 25 SW Pump. May enter AB.SW-0001. May order the start of another idle pump.
PO Manually starts 25 SW Pump or other idle pump as directed by CRS.
Initiates maintenance / troubleshooting activities LCRS SIMULATOR OPERATOR:
Page 6 of 12 NUREG-I021, Draft Revision 9
Time Position Applicant's Actions or Behavior RO ResDonds to alarms (D-16. E-12. E-281. ~~
RO Identifiesfailure of Pzr Press Ch I RO Places Pzr Press Master Controller in MANUAL, adjusts demand to current pressure.
CRS Implements AB.PZR-0001. Directs RO to
- adjust Master Controlleroutput to value obtained from Attachment 1
- select alternate pressure control channel
- return Master Controllerto AUTO RO Selects alternate pressure channel for pressure control RO Places Master Controller in AUTO CRS Directs removal of the failed Pressurizer Pressure Channel from service IAW S2.0P-SO.RPS-O003(Q), Placing Pressurizer Channel In Tripped Condition CRS Refers to TS. Enters TSAS 3.3.1 .I. Action 6 and 3.3.2.1 b. Action19 for failed channel. Enters TSAS 3.4.5b for PORV 2PR1 not operable in AUTO.
CRS/RO Close 2PR6 PORV Stop Valve CRSlRO Direct N E 0 to open breaker for power to 2PR6 PORV Stop Valve SIMULATOR OPERATOR:
Page 7 of 12 NUREG-1021, Draft Revision 9
Op-Test No.: I Scenario No.: 1 Event No.: 4 Event
Description:
21 Containment Fan Coil Unit Trip Time Position Applicant's Actions or Behavior CRS/RO/PO Recognize indications of problem PO Refers to S2.OP-AR.ZZ-0011 (a),for Low Air Flow console alarm PO NOTIFY the SMlCRS to refer to Technical Specifications PO Refers to S2.OP-SO.CBV(Q), to start the standby CFCU (#25)
CRS Enters TS 3.6.2.3 Action a I7 dav LCO)
SIMULATOR OPERATOR:
- 1. When dispatched as NEO, report back odor of burnt insulation. Appears all 21 CFCU breakers affected.
- 2. If directed to rack out breakers, request assistancefrom maintenance electricians because of apparent damage to breaker cubicles.
- 3. Use RT-9 to open 21 CFCU 125 VDC breaker.
Page 8 of 12 NUREG-I021, Draft Revision 9
L Op-Test No.: 1 Scenario No.: 1 Event No.: 5 Event
Description:
Decreasing Condenser Vacuum Position Amlicant's Actions or Behavior CRS/RO/PO Recognize indicationsof decreasing vacuum:
- loss of generator megawatts
- high dissolved oxygen alarm
- rise in condenser backpressure
-Alarm OHA G-5,CNDSR VAC LO
- Alarm OHA G-13, CNDSR VAC LO-LO CRS Implements S2.OP-AB.COND-0001 (a),Loss of Condenser Vacuum. Directs actions IAW procedure
- initiates Attachment 1, Continuous Action Summary
- dispatchesoperators to look for source of problem per Attachment 2
- directs start of all available condenser vacuum pumps
- directs load reduction at 5 5% per min to attempt to stabilize condenser press
- when required (backpressure > limit in Att 4), initiate rapid load reduction
- implement S2.OP-AB.LOAD-0001 (Q), Rapid Load Reduction
-when necessary, orders manual reactor and turbine trips PO Performs actions as directed to address decreasing vacuum:
- dispatchesoperators to look for source of problemper Attachment 2
- starts all available condenser vacuum pumps
- performs turbine load reduction RO Performs actions as directed to address decreasing vacuum:
- dispatches operators to look for source of problem per Attachment 2
- coordinates with PO to reduce turbine and reactor power
- maintains Tavg on program
- energizes pressurizer heaters
- initiates boration SIMULATOR OPERATOR:
- 1. Increase severity of vacuum leak to 100% with no ramp after crew has reduced reactor power 210% or at discretion of lead examiner.
- 2. Use RT-5 to trigger next event (trip of main feed pumps) after increasing size of vacuum leak.
Page 9 of 12 NUREG-1021, Draft Revision 9
Op-Test No.: I Scenario No.: I Event No.: 6 Event
Description:
Both Main Feed Pumps Trip, A M , Pzr Safety 2PR3 Fails Open Time Position Amlicant's Actions or Behavior Recoanizes both main feed wmDs triDDed. Orders manual reactor trim Performs initial actions of EOP-TRIP-I
- 1. MANUAL Reactor Trip:
. First Handle to Trip.
Second Handle to Trip.
RTBs to open.
- E6D and G6D to open.
- 2. Trip not confirmed.
- 3. MANUAL Turbine Trip.
- 4. Initiate Control Rod Insertion.
Transitions to EOP-FRSM-1 CRITICAL TASK #I Manually trip the main turbine within 30 seconds of diagnosis of ATWT conditions.
Verifies AFW flow >44E4 Ibm/hr Starts 21 and 22 Charging Pumps Verifies BITflow and SJI, 2,4,5,12, 13 open Verifies CV40.41.68 &69 closed Verifies > I charging flow 00 Dispatches NE0 to open RTBs and Rod Drive MG Set Breakers Dispatches NE0 to close WR70 andl5ls Verifies SI component actuation IAW APPX-3.
I I RO Ro Verifies all PRNls 5%
Verifies IR startup rate negative I I CRS CRS Directs chemistry to sample RCS Directs STA/Rx Eng to perform SDM calculation I I CRS Returns to EOP-TRIP-1 1 1 CRS/RO/PO Verify immediate actions of EOP-TRIP-1 Stops all RCPs with RCS pressure < I350 psig Verifies equipment alignment per EOP-TRIP-I Page I O of 12 NUREG-1021, Draft Revision 9
Op-Test No.: 1 Scenario No.: 1 Event No.: 6 Event
Description:
Both Main Feed Pumps Trip, A M , Pzr Safety 2PR3 Fails Open CRS/RO/PO Performs diagnostic activities including:
LOSC SGTR LOCA Determines 2PR3 is stuck open CRS Transitions to EOP-LOCA-1 (based on containment sump level 146 or elevated/increasing containment radiation levels)
Performs faulted SG evaluation Performs ruptured SG evaluation RO/PO Resets SI,Phase A, Phase B,opens 21 and 22 CA330, and resets each SEC and resets 230V Control Centers PO Stops RHR Pumps CRS/RO/PO Performs SI flow reduction evaluation CRS Transitions to EOP-LOCA-2 NOTE: Terminate scenario on lead examiners direction after crew has determined that SI flow cannot be reduced.
SIMULATOR OPERATOR:
- 1. Open Reactor Trip Breakers 3 minutes after directed by crew. Delete overrides on RBs, then B440, 8441, RTB A and B open switch to ON. Also, open following breakers:
RT-7, RP07D 21 Rod Drive MG Set Motor Breaker RT-7, RP08D 22 Rod Drive MG Set Motor Breaker Page 11 of 12 NUREG-1021, Draft Revision 9
Time Position Applicants Actions or Behavior CRS Directs PO to perform EOP-APPX-3 PO Determines 23 AB Exh Fan did not start RO Blocks SI to SEC using CMC switches on rear panel PO Resets C SEC I I PO I Starts 23 AB Exhaust Fan NOTE: Terminate scenario on lead examiners direction after crew has determined that SI flow cannot be reduced.
ANTICIPATED EMERGENCY CLASSIFICATION FOR THIS SEQUENCE OF EVENTS:
Site Area Emergency (5.1.3)
Page 12 of 12 NUREG-I021, Draft Revision 9
NRC #1 MODE: 1 POWER: 90% RCS 869 Mwe: 1070 BORON:
SHUTDOWN SAFETY SYSTEM STATUS (5,6 & DEFUELED):
NA REACTIVITY PARAMETERS 4000 MWD/MTU, Zenon burning out slowly at 8 pcm/hr MOST LIMITING LCO AND DATE/TIME OF EXPIRATION:
2A Diesel Generator was C/T 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> ago for injector maintenance. 3.8.1.1 b action b is in effect, the next Line surveillance is due in 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
21 RHR Pump was C/T 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> ago for a coupling alignment. 3.5.2 c, action a. Maintenance on both components expected to be completed 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> from now.
EVOLUTIONS/PROCEDURES/SURVEILLANCESIN PROGRESS :
Raise Power to 100% at lO%/hr. Reactivity Plan recommends 2500 gal of primary water for 10%
power increase, rods to be withdrawn as required for temperature control to All Rods Out position.
ABNORMAL PLANT CONFIGURATIONS:
CONTROL ROOM:
PRIMARY:
SECONDARY:
Heating steam is aligned to unit 1.
RADWASTE:
No discharges in progress CIRCULATING WATEFUSERVICE WATER:
Appendix D Form ES-D-1 I Facility:
Examiners:
SALEM 1 & 2 Scenario No.: NRC #2 Operators:
Op-Test No.: HOTEL Initial Conditions: 100% Rated Thermal Power, BOL, Equilibrium Conditions Turnover: Unit 2 is at 100% power. Unit 1and Hope Creek are also at 100% power. Solar magnetic disturbances have been occurring. Current SMD K3. 22 AFW Pump was taken 0 0 s 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> ago for motor bearing replacement.AFW pump maintenance is expected to be complete 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> from now. All required surveillances are complete. The crew is directed to maintain
,wer.
1 Event No.
Malf. No. Event Event DescriDtion N10193A PRNIS Channel N41 Fails High (TS CRS)
CRSlRO CF81 (OVDI) 24MSlO Relief Fails Open (Pressure Setpoint Decrease)
CRSlPO I ------------
~~
DA033D (RF) Failure of RTB Shunt Trip Capability (TS CRS) 4 TU0081G N Main Turbine Governor Valve 23MS29 Fails Closed CRSlPO R
RO 5 VL0447 C SG Fdwtr Control 22BF19 Fails Closed, Turbine Fails To RP0058 ALL Trip, Auto MSLIS Fails to Actuate RP0069 RP0073 RP0279AtkB 6 EL0144 M Loss of 2A 4KV Vital Bus and 23 AFW Pump Trip AF0183 ALL Terminate when feed flow re-established to a SG
- (N)orr LC (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Page 1 of 10 NUREG-1021, Draft Revision 9
SIMULATOR SETUP INITIAL CONDITIONS I
I. Initialize simulator to IC-I92, 100% power, BOL, C, 1145 ppm
- 2. Clearance tag 22 AFW Pump EVENT TRIGGERS I
I 6. I 2A 4KV Bus Deenergizes on Reactor Trip (Control Bank C < 5 steps) I MALFUNCTION
SUMMARY
No Description Delay Ramp Remote Initial Final I
I Event Value Value
- 1. AN0253, SER 253 Fails: G29 Priming Tank No No NolNo 0 1 I 2. I RP0058, Failure of Auto Rx Trip
____ ~
I No I No I NolNo I NA I True I
- 3. RP0069, Main Turbine Interface Valve Failure No No NolNo NA True
- 4. RP0073, Mn Turbine Trip Failures (Various) No No NolNo 0 4
- 5. RP0279A, Auto MSLIS Fails to Actuate - Tm A No No NolNo NA True I 6. I RP0279B,AutoMSLlSFailstoActuate-Tm B I
~
No I No I NolNo I NA I True I
- 7. N10193A, PR Ch N41 Fails High No No 11No 0 200
- 8. TU0081G, 23MS29 Turb Cntrl Vlv Fails CIS No No 41No NA True
- 9. VL0447,22BF19 Fails Closed3 No 00:02:00 51No NA 0 I I O . I EL0144, Lossof 2A4160VVital Bus I No I No I No16 I NA I True I
- 11. AFOI 83,23 Aux FW Pmp Overspeed Trip' No No 7lNo NA True REMOTE FUNCTION
SUMMARY
I I I I I I No
-~
I ______
Description
~~
I Delay I Ramp I Remote
/Event I Initial Value
~
I Final Value
~
- 1. AF25D, 22 AFW Pump Bkr Control Power No No NolNo off Off
- 2. AF26D, 22 AFW Pump Rack Out No No NolNo Tagged Tagged
- 3. DA033D, 2AADC Bkr # I 4 Rx Trip Bkr No No 31No Closed Open UO OVERRIDE
SUMMARY
1 Page 2 of 10 NUREG-1021, Draft Revision 9
No Description Delay Ramp Remote Initial Final
/Event Value Value
- 2. CF18 OVDI, 24MS10 Press Setpt Decrease No No 2/No off On ATOR OPERATOR NOTES Trip 23 AFW Pump after PO throttles AFW (after immediate actions of EOP-TRIP-1).
II After being dispatched to investigateclosure of Main Turbine Governor Valve, NE0 reports EHC fluid leak on 23MS29 valve actuator.
Insert Malf VL0447,22BF19 Fails Closed (RT-5), after condensate pump stopped during rapid power reduction or at lead examiner's discretion.
Collect trend data on the following for evaluators:
Reactor power Turbine Generator load (MW) 21,22,23,24 SG NR level 21,22,23,24 SG WR level Page 3 of 10 NUREG-1021, Draft Revision 9
Op-Test No.: 1 Scenario No.: 2 Event No.: 1 Event
Description:
PR NIS Channel N41 Fails High Applicant's Actions or Behavior Observe indicationsof channel failure
- numerous alarms on OHA-E
- control rods stepping in
- PR NIS N41 indicatingfull scale high
- PCS AFD alarms Determines PR NIS Channel has failed high. Places ROD BANK SELECTOR SWITCH in MANUAL after obtaining CRS concurrence.
Identifiesfailed channel. Informs CRS.
Refers to S2.OP-SO.RPS-0001 (a),Nuclear Instrumentation Channel TriplRestorationto review actions for removing failed channel from service.
May also enter AB.NIS or AB.ROD-0003.
Notifies IlC Maintenance Reviews TS. Enters LCO 3.3.1.1 Actions 2 and 6 Coordinate to remove channel from service
- 1. DETECTOR CURRENT COMPARATOR, UPPER SECTION to PRN41
- 2. Verify CHANNEL DEFEAT lamp lit and OHA E-38 clears (alarm already cleared - specific NIS failure used does not cause this alarm)
- 3. DETECTOR CURRENT COMPARATOR, LOWER SECTION to PRN41
- 4. Veri@ CHANNEL DEFEAT lamp lit and OHA E 4 6 cleared (alarm already cleared - specific NIS failure used does not cause this alarm)
- 5. POWER MISMATCH BYPASS to BYPASS PR N41
- 6. ROD STOP BYPASS to BYPASS PR N41
- 7. Verify 2RP4-OVERPOWER ROD STOP MANUAL BYPASS, CH 1 lit
- 8. Verify OHA E-31 clear
- 9. COMPARATOR CHANNEL DEFEAT to N41 I O . Verify COMPARATOR DEFEAT lit and OHA E-39 clear
- 11. At Control Rack No. 26, AXIAL FLUX DIFF MONITOR INPUT TEST SWITCH 1 to TEST
- 12. Contact IlC to position bistable test switches
- 13. Remove both AC control power fuses from N41 drawer front Reduce turbine load, if needed to restore Tavg to program If desired. return ROD BANK SELECTOR SWITCH to AUTO SIMULATOR OPERATOR:
- 1. If I/C directed to position bistable test switches, report that technicianwill be available to assist in approximately Ihour.
- 2. Use RT-2 to trigger next event (MS10 fails open) after rods are returned to AUTO.
Page 4 of 10 NUREG-1021, Draft Revision 9
Op-Test No.: I Scenario No.: 2 Event No.: 2 Event
Description:
24MS10 Relief Fails Open (Pressure Setpoint Decrease)
E Position ADDliCanrS Actions or Behavior CRS/RO/PO Observe changing plant parameters (temperature, power, steam pressure) and identify 24MS10 is open.
RO Reports Tavg lowering, Pzr Press Lo E-28 alarm, B/U Htrs energize in Auto alarm PO Attempts to determine reason for excess steam flow CRS Enters AB.STM-0001 (Q), Excessive Steam Flow. InitiatesAttachment 1 CAS.
PO Reports turbine electro-hydrauliccontrol working correctly CRS Directs RO and PO to prepare for load reduction NOTE: 24MS10 failure may be diagnose and valve closed prior to any load reduction.
~
PO Takes manual control, closes 24MS10.
CRS Initiates action to reDair controller.
SIMULATOR OPERATOR
Page 5 of 10 NUREG-I021, Draft Revision 9
Op-Test No.: 1 Scenario No.: 2 Event No.: 3 Event
Description:
Failure of RTB Shunt Trip Capability (TS CRS)
I I Time Position Applicant's Actions or Behavior RO Observes console alarm. Refers to S2.SO-AR.ZZ-O012(Q), 2CC2 Console Alarm Procedure.
CRS Determines that shunt trip capability (not UV trip capability) is affected.
Refers to TS. Enters TS LCO 3.3.1 .IAction 14 (not Action 1).
CRS Initiates actions to reDair RTB.
SIMULATOR OPERATOR:
Page 6 of 10 NUREG-1021, Draft Revision 9
Op-Test No.: 1 Scenario No.: 2 Event No.: 4 Event
Description:
Main Turbine Governor Valve 23MS29 Fails Closed Position Applicant's Actions or Behavior CRS/RO/PO Observe indications of valve closure:
- Megawatt load will drop rapidly as remaining governor valves open until limited by valve position limiter (VPL)
- Console Alarm TavglTref dev as Tavg rises.
- Steam Dumps will open to attempt to control Tavg
- Pressurizer pressure and level will rise due to change in Tavg, sprays open to control Dressure PO Determines that 23MS29 has closed. Informs CRS. Dispatches NE0 to investigate.
CRS Refers to Precautionsand Limitations of S2.OP-SO.TRB-0001 (a),Turbine Generator Startup Operations. Determines need to reduce power to 5 30% at 5%
per minute. Implements S2.OP-AB.LOAD-0001(Q), Rapid Load Reduction NOTE: CRS may direct >5% per min load reduction until functioning governor valves are off of open limit.
RO Initiates power reduction using rods and boration. Energizes pressurizerheaters.
Maintains rods above Rod Insertion Limit.
I I PO CRS Initiates turbine load reduction.
Dispatches maintenance to investigateproblem with governor valve.
CRS Notifies electric system operator and operations management.
PO Stops one condensate pump at -75% power.
SIMULATOR OPERATOR:
- 5. After being dispatched to investigate closure of Main Turbine Governor Valve, NE0 reports EHC fluid leak on 23MS29 valve actuator.
- 6. Use RT-5 to trigger next event (22BF19 closes) after condensate pump is stopped or at discretionof lead examiner.
Page 7 of 10 NUREG-1021, Draft Revision 9
Op-Test No.: 1 Scenario No.: 2 Event No.: 5 Event
Description:
SG Fdwtr Control 22BF19 Fails Closed, Turbine Fails To Trip Time Position Applicant's Actions or Behavior PO Responds to feedwater alarms and/or notes changes in BFI 9 position.
PO Determines 22BF19 is closed, attempts to open in MANUAL, reports that it will not oDen.
CRS Orders a manual reactor trip.
RO Manually trips reactor RO Attempts to trip turbine. Determines turbine trip not functioning.
CRITICAL TASK #I lnltlates MSLl before completion of reading of first 4 steps of EOP-TRIP-I.
RO Determines MSLl required. Manually initiates MSLIS I CRS I Implements EOP-TRIP-I SIMULATOR OPERATOR:
- 7. 2A 4KV Bus will automatically de-energize on event trigger when Control Bank C < 5 steps.
Page 8 of I O NUREG-1021, Draft Revision 9
Op-Test No.: 1 Scenario No.: 2 Event No.: 6 Event
Description:
Loss of 2A 4 W Vital Bus and 23 AFW Pump Trip Time Position Applicants Actions or Behavior CRS Performs initial actions of EOP-TRIP-1
- Trip Reactor (had to manually trip)
- Is Reactor Trip Confirmed
- Trip Turbine (turbinewould not trip, MSlVs closed)
- Is ANY 4 KV Vital Bus energized (2A de-energized)
- Is SI Actuated (SI will actuate because of failure of turbine trip)
RO Reports reactor tripped manually, 2 rods not fully inserted RO Reportsturbine not tripped, MSlVs closed PO ReDorts 2A 4KV Bus de-eneraized. 21 EDG runnina unloaded CRS NOTE: Mn generator output bkrs do not auto open because turbine fails to trip. CRS may order opening of mn gen output bkrs 1-9 and 9-10 CRS Makes page announcement - reactor trip CRS Notifies SM of need to implement Emergency ClassificationGuide I PO Controls AFW flow to maintain >22E04 lblhr NOTE: Use RT-7 t o trigger trip of 23 AFW pump after PO throttles AFW (after immediate actions of EOP-TRIP-1).
RO Verifies RCPs running, Tavg trending to 547F, trip breakers open PO PO reports loss of flow on 23 AFW Pump.
CRS Dispatches NE0 to close 21SW20 (2A bus component)
CRS Requests assistance from WCC to perform AB.4KV-0001 and investigate loss of 2A 4KV Bus CRS Directs RO to start 22 SWGR Exh Fan NOTE: Fan appears to be running - bkr is closed but bus is de-energized RO Reports only 1 CCW pump running.
CRS Dispatches NE0 to close CC37 and CC38 CRS Directs transition to FRHS-1 when SG level ~ 9 % with AFW flow <22E04 Ib/hr CRSIROIPO Verify RCS pressure > intact SG pressure CRS Reviews Bleed and Feed initiation criteria with crew RO Stops all reactor coolant pumps PO Verifies condensate system in operation PO Reports SGFP not available due to MSLl RO Initiates SI Page 9 of I O NUREG-I021, Draft Revision 9
Op-Test No.: 1 Scenario No.: 2 Event No.: 6 Event
Description:
Loss of 2A 4KV Vital Bus and 23 AFW Pump Trip
~
Position Applicant's Actions or Behavior CRS Directs SI Verification per EOP-APPX-3 RO Resets SI Resets Phase A Isolation Resets Phase B Isolation Opens 21CA330 and 22CA330 Resets each SEC Resets 230V Control Centers RO Stops running RHR and SI pumps. Stops either 21 or 22 Charging Pump I
CRS I
I Determines SG to be depressurized.
PO II Fully opens selected MSIO CRS II Directs NE0 to open selected BF40 or BF19 PO I Opens selected BF13 I
PO I Opens 21CN48 and 22CN48 PO Closes 21CN32 and 22CN32 PO I Reports observed level increase in selected SG and/or CET temperatures lowerina
- - u CRITICAL TASK #2 Establish condensate flow into at least one SG.
NOTE: Terminate scenario on lead examiner's direction after condensate flow has been established.
SIMULATOR OPERATOR:
- 1. 2A 4 W Bus will automatically de-energize on event trigger when Control Bank C .c 5 steps.
- 2. Use RT-7 to trigger trip of 23 AFW pump after PO throttles AFW (after immediate actions of EOP-TRIP-1).
ANTICIPATED EMERGENCY CLASSIFICATION FOR THIS SEQUENCE OF EVENTS:
Site Area Emergency (3.1.1.b AND 3.2.1.b)
. OR Site Area Emergency (8.1.3.c)
Page 10 of 10 NUREG-1021, Draft Revision 9
NRC #2 MODE: 1 POWER: 100% RCS 1145ppm Mwe: 1190 BORON:
SHUTDOWN SAFETY SYSTEM STATUS ( 5 , 6 & DEFUELED):
NA REACTIVITY PARAMETERS 4000 MWDMTU MOST LIMITING LCO AND DATE/TIME OF EXPIRATION:
22 AFW Pump was C/T 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> ago for motor bearing replacement, 3.7.1.2 a, action a.
Maintenance is expected to complete 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> fiom now.
EVOLUTIONS/PROCEDURES/SURVEILLANCESIN PROGRESS:
Orders to shift to maintain 100% power.
ABNORMAL PLANT CONFIGURATIONS:
CONTROL ROOM:
Solar Magnetic Disturbances have been occurring, currently there is an SMD K-3 in effect until 2300 tonight.
PRIMARY:
SECONDARY:
Heating steam is alignec, to mlr ..
RADWASTE:
No discharges in progress CIRCULATING WATEWSERVICE WATER:
Appendix D Form ES-D-1 Facility: SALEM 1 & 2 Scenario No.: NRC #3 Op-Test No.: HOTEL Examiners: Operators:
1 Initial Conditions: 3% Rated Thermal Power, MOL Turnover: Unit 2 is at 3% power, recovering from a 7 day forced outage to repair body to bonnet leak on Pzr Spray Bypass Valve 2PS4. Mode change is approved. Weather conditions are normal. Unit 1and Hope Creek are at 100% power. Shift orders are to raise power in preparation for placing the main turbine in service. Procedure in use: IOP-3 at Step 5.4.14.
Event Malf. No. Event Event TYPe* Description 1 N Raise Reactor Power CRSlPO R
RO 2 PROOI7A I Pressurizer Level Channel I (LT459) Fails Low (TS CRS)
CRSlRO 3 SG0078A C 21 SG Tube Leak (5 gpm) (TS CRS)
ALL 4 BFOI05A C 21 Main Feed Pump Trip CRSlPO 5 RCOOIPC C 23 RCP High Vibration CRSlRO 6 SG0078A M SGTR with Loss of Offsite Power EL0134 ALL 7 SJOI84A C 21 SI Pump Fails to Auto Start CRSlPO Terminate scenario when depressurization criteria met (SGTR-1 Table F)
- (N)ormal, (R)eactivity, Page 1 of I O NUREG-I021, Draft Revision 9
SIMULATOR SETUP INITIAL CONDITIONS
- 1. Initialize simulator to 3% power IC-I 93 EVENT TRIGGERS I
I. None MALFUNCTION
SUMMARY
Description AN0253, SER 253 Fails: G29 Priming Tank I Delay No R i p 1 I I I f;;;R e
Event NoINo lnil Value Fiial Value PRO017A, Pzr Lvl Ch I (LT459) Failure No SG0078A, 21 SG Tube Leak I No I 4. I BF0105A, 21 Main Feed Pump Trip
~~
I No
- 5. RC0012C, 23 RCP High Vibration No
- 6. EL0134, Loss of Offsite Power' No
- 7. SJ0184A, 21 SI Pp Fails to Start on SEC I No I No NoINo NA True REMOTE FUNCTION
SUMMARY
I I I I I I No Description Delay Ramp Remote Initial Final
/Event Value Value
- 1. None 110 OVERRIDE
SUMMARY
I I I I I I No Description Delay Ramp Remote Initial Final
/Event Value Value
- 1. None Page 2 of 10 NUREG-1021, Draft Revision 9
SIMULATOR OPERATOR NOTES I
1 1. After 23 RCP High Vibration, ramp the severity of the SG tube leak from 5 gpm to 650 gpm over 3 minutes, then initiate the loss of offsite power.
- 2. Collect trend data on the following for evaluators:
21 and 22 SG pressure Pzr pressure 21 and 22 SG NR level Highest CET temperature NI power
- 3. If contacted on SG tube leak, SM informs CRS that extra NCO will perform rad monitor plotting IAW Continuous Action Summary Steps 3 and 4 of S2.SO-AB.SG-0001 (Q).
Page 3 of 10 NUREG-I021, Draft Revision 9
Op-Test No.: 1 Scenario No.: 3 Event No.: 1 Event
Description:
Raise Reactor Power Time Position Applicant's Actions or Behavior CRS Directs activities associated with power increase IAW S2.OP-IO.ZZ-O003(Q), Hot Standby to Minimum Load:
- rod motion
- dilution CRS Initiates Turbine Generator Startup Operations RO Adds positive reactivity
- rod motion I I I PO I
I I
-dilution 1I Places MSlOs in AUTO with setpoint I010 to 1020 psig I
SIMULATOR OPERATOR:
Page 4 of 10 NUREG-I021, Draft Revision 9
Op-Test No.: I Scenario No.: 3 Event No.: 2 Event
Description:
Pressurizer Level Channel I (LT459) Fails Low Time Position Andicant's Actions or Behavior RO Observes OHA. Identifiesthat Pzr Lvl Ch I has failed low.
CRS/RO Refers to Alarm ResDonse Procedure for OHA E-36.
RO Takes manual control of charging, minimizes charging flow (maintains pzr level on pgrm IAW AB.CVC Attachment 1).
NOTE: FromAttachment 1. Taraet Pzr Level = 1.1875 * (Tava - 547) + 22 Selects an oaerable channel for control. alarm. and recorder.
RO Restores pressurizer heaters, as desired.
CRS Directs restoration ofletdown IAW S2.OP-S0.CVC-0001 (Q), Charging, Letdown and Seal Injection NOTE: CRS may go directly to AB.CVC-0001(a),Loss of Charging. Steps that are duplicated in AB are shown here in bold italics.
RO Prepares for letdown restoration:
- 2. Ensures letdown orifice isolations closed (2CV3,4, 5)
- 3. Ensures 2CC71 in AUTO
- 4. Opens 2CV7, Ltdn Hx Inlet Vlv
- 5. Places 2CV18 in MANUAL CLOSE
- 6. Opens 2C18 until CLOSE (INC PRESS) p/b extinguishes
- 7. Opens 2CV2 (and 2CV277), Ltdn Line lsol Vlv(s)
- 8. Places 2CV2 and 2CV277 (Ltdn Line /sol Vlvs) in AUTO
- 9. Places 23 Charging Pump in MANUAL andADJUSTS chg flow 85-90 gPm I O . Adjusts 2CV71, as necessary, to maintain 6-12 gpm per pump, not to exceed 40 gpm total RCP seal injection flow RO Restore letdown:
- 1. Simultaneously
- Opens 75 gpm letdown orifice isolation (2CV4 or 2CV5)
- Adjusts 2CV71 for 6 to 12 gpm per pump
- Adjusts 2CV18 to maintain letdown pressure at 300 psig
- 2. Ensures Master Lvl Controller in AUTO
- 3. Ensures pzr level within normal band, places 23 Chg pump in AUTO
- 4. Adjusts 2CV18 as necessary and places in AUTO CRS Contacts I&C to place pressurizer channel in tripped condition (/AW S2.OP-SO.RPS-O003(Q), Placing Pressurizer Channel in Tripped Condition.)
CRS Enters TS LCO 3.3.1 .I Action 6. May review post accident monitoring TS (only 2 channels required).
SIMULATOR OPERATOR:
- 1. Use RT-2 to trigger next event (SG Tube Leak) after normal letdown has been restored on cue from lead examiner.
Page 5 of 10 NUREG-I021, Draft Revision 9
r
~~
Op-Test No.: I Scenario No.: 3 Event No.: 3 Event
Description:
21 SG Tube Leak (5 gpm)
Time Position Applicant's Actions or Behavior PO Reports increasing activity in cond offgas (R15) and 21 SG BID Sample (R19A)
CRS Refers to AB.RAD-0001(Q), Abnormal Radiation NOTE May go directly to AB.SG-0001(Q), Steam Generator Tube Leak CRS Announces increasina activitv on 21 SG CRS Notifies SM to refer to Emergency ClassificationGuide CRS Refers to AB.SG-0001 (Q), Steam Generator Tube Leak CRS Reviews Attachment 1, CAS.
RO Verifies pressurizer level stable RO/PO Identifies21 SG as affected SG I I PO ~
I~~
Sets 21MSI 0 to 1045 psig
~ ~ ~ ~ _ _ _ _
PO Closes 21GB4,21 MSI 8,21 MS7 CRS Dispatches NE0 to close 21MS45,23 AFW Pump Turbine Steam Supply CRS Dispatches operators to align SGBD and sampling CRS Directs chemistry to sample and determine leak rate RO Calculates RCS leak rate CRS Makes notifications CRS Enters TS LCO 3.4.7.2.c. Action b. for greater than 1 gpm total SG tube leakage and greater than 500 gpd tube leakage in single SG (4 hrs to fix or next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> to Hot Standby)
Page 6 of 10 NUREG-I021, Draft Revision 9
Op-Test No.: 1 Scenario No.: 3 Event No.: 4 Event
Description:
21 Main Feed Pump Trip I Time CRS Position Applicant's Actions or Behavior Recognizes trip of the operating main feedwater pump. Enters S2.0P-AB.CN-0001(a),Main Feedwater / Condensate System Abnormality..
l I CRS I Verifies reactor power c P-10 setpoint. Proceeds to Step 3.14.
CRS Directs RO to reduce power to 4%.
PO 4. Sets SG Inlet Vlv demand to 0% (Vlvs 21 through 24AF21)
- 5. Starts 21 and 22 AFW pumps
- 6. Controls 21 through 24AF21 to maintain SG levels within 55% of program level (-35% NR level)
SIMULATOR OPERATOR:
- 7. Use RT-4 to trigger next event RCP High Vibration) on after SG level control established or following plant stabilization post-trip on cue from lead examiner.
Page 7 of 10 NUREG-1021, Draft Revision 9
~~
Op-Test No.: 1 Scenario No.: 3 Event No.: 5 Event
Description:
23 RCP High Vibration Time I Position Applicant's Actions or Behavior RO Observes OHA D-36 RCP VIB HI alarm. Refers to S2.OP-AR.ZZ-O004(Q),
Overhead Annunciators Window D.
PO Checks vibration levels behind Panel 2RP4. Determines vibration level on 23 RCP motor flanae > 5 mils.
CRS Implements S2.OP-AB.RCP-0001 (a), Reactor Coolant Pump Abnormality.
InitiatesAttachment 1 , Continuous Action Summary.
CRS Directs manual reactor trip and stop of 23 RCP after reactor trip confirmed.
NOTE If reactor already tripped, then CRS will direct stopping #23 RCP.
SIMULATOR OPERATOR:
- 2. Use RT-5 to trigger next event (Loss of Offsite Power) when S I manually initiated or at discretion of lead examiner.
Page 8 of 10 NUREG-I021, Draft Revision 9
Op-Test No.: 1 Scenario No.: 3 Event No.: 6 Event
Description:
SGTR with Loss of Offsite Power Position Applicant's Actions or Behavior RO/PO Observe indicationsof increased rate of 21 SG tube leakage. Informs CRS.
CRS Directs manual SI actuation. Makes page announcement. Transitions to EOP-TRIP-I.
CRS/RO/PO Perform immediate actions of EOP-TRIP-1.
CRS Directs PO to perform APPX-1 to restart CCW pump.
CRS Confirms operability of 4Kv vital buses following loss of offsite power, remains in
~~
PO Blocks and resets SECs RO Verifies no RCPs running and Tavg 6 4 7 . (Step 21)
PO Throttles AFW to maintain SG NR levels 9-35% (Step 21)
PO Initiates MSL Isolation on loops 21 through 24 (Step 21)
CRITICAL TASK # I IsolateAFW to the ruptured SG within' 10 minutes of initiation of Safety Injection signal.
PO Isolates AFW to 21 SG CRS Determines 21 SG level increasing in an uncontrolledmanner. Transitions to EOP-SGTR-1 (From Step 27 of EOP-TRIP-1)
PO Verify valves closed on ruptured SG (Step 4)
MS167 MS Stop MS18 MS Bypass MS7 MS Drain GB4 SG Outlet PO Stops feeding 21 SG (Step 6).
NOTE CRS may direct tripping 23 AFW Pump until stm isolated from 21 SG Resets SI, Phase A, Phase B, SECs, and opens cntmt control air isolation valves 121CA330 and 22CS330). Resets 230V Control Centers (Stet) 10).
CRS Determines taraet cooldown CET temDerature from Table D.
PO Cooldowns at max rate using intact SG MSIO valves. Stops cooldown at target temperature.
PO Depressurizes RCS using PORV NOTE Terminate scenario when depress criteria met (SGTR-1Table F) or at discretion of lead examiner.
Page 9 of 10 NUREG-1021, Draft Revision 9
Time Position Applicants Actions or Behavior PO Determines 21 SI Pump failed to start.
~
CRS Directs PO to reset SEC and start 21 SI Pumo PO Resets A SEC PO Manually starts 21 SI Pump.
1 PO Informs CRS.
NOTE Terminate scenario when depress criteria met (SGTR-1TableF) or at discretion of lead examiner.
Page 10 of 10 NUREG-1021, Draft Revision 9
NRC #3 MODE: 2 POWER 3% RCS Mwe: 0 BORON:
SHUTDOWN SAFETY SYSTEM STATUS (5,6 & DEFUELED):
NA REACTIVITY PARAMETERS 4000 MWDMTU Reactivity plan for power increase recommends using rod withdrawal to control Tavg during power increase to 18%. Detailed reactivity plan for power increase after turbine sync being developed by Rx engineering MOST LIMITING LCO AND DATE/TIME OF EXPIRATION:
None EVOLUTIONS/PROCEDURES/SURVEILLANCESIN PROGRESS:
Plant is recovering fiom a 7 day forced outage to repair a body to bonnet leak on2Ps4. Currently at step 5.4.14 in IOP-3 awaiting Chemistry Department samples. All mode change signoffs are completed.
ABNORMAL PLANT CONFIGURATIONS:
CONTROL ROOM:
PRIMARY:
SECONDARY:
Heating steam is aligned to unit 1.
RADWASTE:
No discharges in progress CIRCULATING WATEWSERVICE WATER: